CN115896589B - Oxide dispersion strengthening FeCrAl alloy and preparation method and application thereof - Google Patents
Oxide dispersion strengthening FeCrAl alloy and preparation method and application thereof Download PDFInfo
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- 229910045601 alloy Inorganic materials 0.000 title claims abstract description 94
- 238000002360 preparation method Methods 0.000 title claims abstract description 32
- 239000006185 dispersion Substances 0.000 title claims abstract description 20
- 238000005728 strengthening Methods 0.000 title claims abstract description 18
- 238000000034 method Methods 0.000 claims abstract description 32
- 239000000463 material Substances 0.000 claims abstract description 28
- 238000005253 cladding Methods 0.000 claims abstract description 22
- 239000000843 powder Substances 0.000 claims abstract description 22
- 239000000446 fuel Substances 0.000 claims abstract description 15
- 238000005551 mechanical alloying Methods 0.000 claims abstract description 14
- 238000005245 sintering Methods 0.000 claims abstract description 13
- 239000000243 solution Substances 0.000 claims abstract description 10
- 239000006104 solid solution Substances 0.000 claims abstract description 9
- 238000005242 forging Methods 0.000 claims abstract description 5
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- Y—GENERAL TAGGING OF NEW TECHNOLOGICAL DEVELOPMENTS; GENERAL TAGGING OF CROSS-SECTIONAL TECHNOLOGIES SPANNING OVER SEVERAL SECTIONS OF THE IPC; TECHNICAL SUBJECTS COVERED BY FORMER USPC CROSS-REFERENCE ART COLLECTIONS [XRACs] AND DIGESTS
- Y02—TECHNOLOGIES OR APPLICATIONS FOR MITIGATION OR ADAPTATION AGAINST CLIMATE CHANGE
- Y02E—REDUCTION OF GREENHOUSE GAS [GHG] EMISSIONS, RELATED TO ENERGY GENERATION, TRANSMISSION OR DISTRIBUTION
- Y02E30/00—Energy generation of nuclear origin
- Y02E30/30—Nuclear fission reactors
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Abstract
The invention discloses a preparation method of an oxide dispersion strengthening FeCrAl alloy, which comprises the following steps: mixing the element powder according to the component formula of the FeCrAl alloy, and preparing oxide dispersion strengthening FeCrAl alloy powder by using a mechanical alloying method; placing the alloy powder into a die, and sintering by using a discharge plasma method to obtain compact blank alloy; removing the die, and performing high-temperature solution treatment on the compact blank alloy to obtain a solid solution alloy; forging and hot rolling the solid solution alloy to obtain the oxide dispersion strengthening FeCrAl alloy. The preparation method of the oxide dispersion strengthening FeCrAl alloy can effectively improve the high-temperature oxidizing property of the material, strengthen the high-temperature strength and shape of the material and enable the material to meet the design requirements of new-generation fuel cladding through proper material component design and reasonable alloy preparation method optimization.
Description
Technical Field
The invention particularly relates to a powder metallurgy preparation method of ODS FeCrAl alloy for nuclear reactor accident fault-tolerant fuel cladding, the ODS FeCrAl alloy prepared by the preparation method and application thereof.
Background
The nuclear reactor fuel cladding is the first safety barrier to contain radioactive materials, and its reliability is an important guarantee for safe operation of the nuclear reactor. As a main commercial material of the pressurized water reactor fuel assembly at present, the conventional zirconium alloy fuel cladding can react with water at high temperature to generate a large amount of hydrogen so as to cause a series of explosions, which is also one of main reasons for the nuclear accident of the fowls island. In order to improve the inherent safety of the fuel cladding under the severe accident condition, the main nuclear power country starts the research and development of a new generation of accident fault tolerant fuel (ATF) cladding successively, and provides a larger safety margin for the reactor under the severe accident condition, and related research draws extensive attention and importance. FeCrAl alloy has excellent comprehensive properties such as high strength, high-temperature oxidation resistance, strong radiation resistance and the like, and becomes an important candidate material for the new-generation ATF cladding.
Because the nuclear reactor fuel cladding is subjected to severe complex service environments such as high temperature, high pressure, corrosion, irradiation and the like, the comprehensive properties of the materials such as high temperature stability, mechanical properties and the like of the existing FeCrAl alloy are difficult to meet the design requirements. The large thermal neutron loss due to the high neutron absorption cross section is one of the main problems restricting the development and application of FeCrAl alloys. Therefore, the strength of the FeCrAl alloy is improved, the mechanical property requirement is met by using a fuel cladding with a thinner wall thickness, and the sub-economy and the competitiveness of the fuel cladding can be effectively improved.
Related researches show that the Oxide Dispersion Strengthening (ODS) FeCrAl alloy prepared by the powder metallurgy method has the advantage that the mechanical property is remarkably improved on the basis of keeping the high-temperature oxidation resistance. On the premise of meeting the mechanical property requirement, the thickness required by the ODS FeCrAl cladding tube can be effectively reduced, so that neutron loss is greatly reduced. However, no mature alloy component design scheme and preparation method are available at present. M still exists in the traditional smelting method 23 C 6 The introduction of equal particles, difficult regulation and control of the size of a disperse phase, element segregation and the like.
The foregoing background is only for the purpose of providing an understanding of the inventive concepts and technical aspects of the present invention and is not necessarily prior art to the present application and is not intended to be used to evaluate the novelty or the inventive step of the present application in the event that no clear evidence indicates that such is already disclosed prior to the filing date of the present application.
Disclosure of Invention
In view of the above, the present invention aims to overcome the defects of the prior art, and to provide a powder metallurgy preparation method of an ODS FeCrAl alloy for accident-tolerant fuel cladding.
In order to achieve the above purpose, the present invention adopts the following technical scheme:
the preparation method of the oxide dispersion strengthening FeCrAl alloy comprises the following steps:
mixing the element powder according to the component formula of the FeCrAl alloy, and preparing oxide dispersion strengthening FeCrAl alloy powder by using a mechanical alloying method;
placing the alloy powder into a die, and sintering by using a discharge plasma method to obtain compact blank alloy;
removing the die, and performing high-temperature solution treatment on the compact blank alloy to obtain a solid solution alloy;
forging and hot rolling the solid solution alloy to obtain the oxide dispersion strengthening FeCrAl alloy.
According to some preferred embodiments of the present invention, the FeCrAl alloy comprises the following components in weight percent: 12.5 to 14.5wt.% Cr,4.5 to 6.0wt.% Al,1.5 to 2.5wt.% Mo,1.0 to 1.5wt.% Nb,0.15 to 0.25wt.% Re,0.10 to 0.15wt.% Y 2 O 3 The balance being Fe and impurity elements.
The application adds Mo, nb, re, Y elements on the basis of main constituent elements of Fe, cr and Al and determines the preferred element content and element addition form. The basic mechanical property and the oxidation resistance of the material are ensured by controlling the contents of Cr and Al elements; adding a proper amount of Mo, nb, re, Y elements and controlling mechanical alloying parameters to form uniformly dispersed fine second phase particles in the alloy, so that the mechanical properties of the alloy are improved; by controlling the proportion of Mo, nb, re and Y elements and the spark plasma sintering parameters, the reduction of mechanical properties caused by coarsening of fine second-phase particles under the influence of long-term high temperature is avoided. The steam oxidation rate of the alloy material prepared by the method is far lower than that of the current commercial nuclear power cladding material Zr-4 under the condition of 1200 ℃, and the alloy material has excellent high-temperature oxidation resistance; the second phase particles which are distributed in a tiny dispersion way are formed in the alloy microstructure, so that the mechanical property of the alloy is obviously improved.
According to some preferred embodiments of the present invention, the total weight percentage content of Mo and Nb is 3% or more, which is effective to stabilize the deformation and to increase the strength of the material by forming Laves-equal dispersed hard phases in the alloy.
According to some preferred implementation aspects of the invention, the total weight percentage content of Re and Y is more than or equal to 0.3%, so that more uniform and fine composite oxides are generated in the alloy, the impurity of grain boundaries is reduced, the dispersion strengthening effect of the alloy is enhanced, and meanwhile, the thermal stability and high-temperature oxidation resistance of the alloy can be effectively improved.
According to some preferred embodiments of the present invention, the ratio of the total weight of Mo and Nb to the total weight of Re and Y is not less than 9, avoiding the problem of performance degradation due to excessive size of the dispersed second phase.
According to some preferred embodiments of the invention, Y is added in the form of Y 2 O 3 Powder, the rest elements are added in the form of simple substance powder.
According to some preferred embodiments of the invention, high purity Ar gas is continuously introduced during the mechanical alloying process.
According to some preferred embodiments of the invention, the mechanical alloying ball milling time is 12-18h and the ball to material ratio is 10-14:1. Preferably, the ball milling time of the mechanical alloying is 15h, and the ball-to-material ratio is 12:1.
According to some preferred embodiments of the invention, the mechanically alloyed ball milling is divided into two stages, wherein in the first stage, the ball milling speed is 80-120 rpm, and the ball milling time is 1-3 hours; in the second stage, the ball milling speed is 200-230 rpm, and the ball milling time is 11-15h. Preferably, the ball milling speed in the first stage is 80-120 rpm, and the ball milling time is 2 hours; the ball milling speed in the second stage is 200-230 rpm, and the ball milling time is 13h. The powder fluidity and the size reach the preferred range by a staged ball milling mode, and the uniform mixing and alloying of the powder are realized.
According to some preferred implementation aspects of the invention, the temperature rising rate is controlled to be 80-120 ℃/min, the pressure is controlled to be 40-60MPa, the temperature is controlled to be 1000-1200 ℃, the sintering time is controlled to be 15-45min, and the vacuum degree is less than or equal to 0.1Pa in the spark plasma sintering process. Preferably, the temperature rising rate is controlled to be 100 ℃/min, the pressure is 50MPa, the temperature is 1100 ℃, the sintering time is 30min, and the vacuum degree is less than or equal to 0.1Pa in the spark plasma sintering process.
According to some preferred embodiments of the invention, the high temperature solution treatment is carried out at a temperature of 1000-1400 ℃ for a holding time of 1-3 hours. Preferably, the temperature of the high-temperature solution treatment is 1150 ℃ and the heat preservation time is 2 hours.
The invention also provides an oxide dispersion strengthening FeCrAl alloy prepared by the preparation method.
The invention also provides application of the oxide dispersion strengthening FeCrAl alloy prepared by the preparation method in nuclear reactor accident fault-tolerant fuel cladding.
Due to the adoption of the technical scheme, compared with the prior art, the invention has the following advantages: the preparation method of the oxide dispersion strengthening FeCrAl alloy introduces a spark plasma sintering technology to realize the efficient preparation of materials, and has the advantages of simple operation, uniform heating, low sintering temperature, short preparation time, uniform material structure and the like compared with the conventional powder metallurgy methods such as hot extrusion, hot isostatic pressing and the like; through proper material composition design and reasonable alloy preparation method optimization, the high-temperature oxidizing property of the material can be effectively improved, the high-temperature strength and the shaping of the material are enhanced, and the design requirements of a new-generation fuel cladding can be met.
Detailed Description
In order to make the technical solution of the present invention better understood by those skilled in the art, the technical solution of the present invention will be clearly and completely described in conjunction with the embodiments of the present invention, and it is apparent that the described embodiments are only some embodiments of the present invention, not all embodiments. All other embodiments, which can be made by those skilled in the art based on the embodiments of the present invention without making any inventive effort, shall fall within the scope of the present invention.
According to the preparation method of the oxide dispersion strengthening FeCrAl alloy, the uniform mixing of powder and the formation of alloying are realized through staged ball milling; and a spark plasma sintering technology is introduced, and the efficient preparation of the material is realized through the optimized parameters. Compared with the conventional powder metallurgy methods such as hot extrusion and hot isostatic pressing, the method has the advantages of simplicity in operation, uniformity in heating, low sintering temperature, short preparation time, uniformity in material structure and the like, and can effectively improve the high-temperature oxidizing property of the material, enhance the high-temperature strength and shaping of the material by proper material composition design and reasonable alloy preparation method optimization, so that the method can meet the design requirements of new-generation fuel cladding.
Example 1
The powder metallurgy preparation method of the FeCrAl alloy for the nuclear reactor accident fault-tolerant fuel cladding comprises the following steps:
step (1), each element and Y are mixed according to the FeCrAl alloy component formula 2 O 3 The powder was mixed (alloy formulation shown as number (1) in table 1 in weight percent) and odds FeCrAl alloy powder was prepared by mechanical alloying.
The mechanical alloying ball milling time is 15h, and the ball-material ratio is 12:1. Specifically, the ball milling process is divided into two stages: in the first stage, the speed is 100rpm, and the time is 2 hours; in the second stage, the speed is 220rpm, and the time is 13h; high-purity Ar gas is continuously introduced in the whole process.
And (2) placing the alloy powder prepared in the step (1) into a steel mold, and sintering by using a discharge plasma method to enable the alloy powder to be in a compact state.
The temperature rising rate is controlled to be 100 ℃/min, the pressure is 50MPa, the temperature is 1100 ℃, the sintering time is 30min, and the vacuum degree is 0.1Pa.
And (3) removing the die, and carrying out heat preservation at 1150 ℃ for 2h high-temperature solution treatment on the compact blank alloy obtained in the step (2) to obtain the solid solution alloy.
And (4) forging and hot-rolling the solid solution alloy obtained in the step (3) to obtain the ODS FeCrAl alloy.
Example 2
The powder metallurgy preparation method of the FeCrAl alloy for the nuclear reactor accident fault-tolerant fuel cladding comprises the following steps:
step (1), each element and Y are mixed according to the FeCrAl alloy component formula 2 O 3 The powder was mixed (alloy formulation shown as number (2) in table 1 in weight percent) and odds FeCrAl alloy powder was prepared by mechanical alloying.
The mechanical alloying ball milling time is 15h, and the ball-material ratio is 12:1. Specifically, the ball milling process is divided into two stages: in the first stage, the speed is 100rpm, and the time is 2 hours; in the second stage, the speed is 220rpm, and the time is 13h; high-purity Ar gas is continuously introduced in the whole process.
And (2) placing the alloy powder prepared in the step (1) into a steel mold, and sintering by using a discharge plasma method to enable the alloy powder to be in a compact state.
The temperature rising rate is controlled to be 100 ℃/min, the pressure is 50MPa, the temperature is 1100 ℃, the sintering time is 30min, and the vacuum degree is 0.1Pa.
And (3) removing the die, and carrying out heat preservation at 1150 ℃ for 2h high-temperature solution treatment on the compact blank alloy obtained in the step (2) to obtain the solid solution alloy.
And (4) forging and hot-rolling the FeCrAl alloy obtained in the step (3) to obtain the ODS FeCrAl alloy.
Comparative example 1
The powder metallurgy preparation method of the FeCrAl alloy of this comparative example is different from that of example 1 in that: in the step (1) of the comparative example, the mechanical alloying ball milling time is 15h, the ball-to-material ratio is 12:1, the ball milling speed is 100rpm, and high-purity Ar gas is not introduced in the process. The remaining steps are the same.
Comparative example 2
The powder metallurgy preparation method of the FeCrAl alloy of this comparative example is different from that of example 1 in that: in the step (2) of the comparative example, the control temperature of the spark plasma sintering process is 800 ℃, and the sintering time is 30min; in the step (3), the compact blank alloy is not subjected to high-temperature solution treatment. The remaining steps are the same.
Comparative example 3
The powder metallurgy preparation method of the FeCrAl alloy of this comparative example is different from that of example 2 in that: the alloy formulation of this comparative example is shown in Table 1 as number (3) in weight percent, Y is added in elemental form, and Y is not added 2 O 3 An oxide.
Comparative example 4
The powder metallurgy preparation method of the FeCrAl alloy of this comparative example is different from that of example 2 in that: the alloy formulation of this comparative example is shown in table 1 as number (4) in weight percent, with no Nb added.
Comparative example 5
Comparative exampleThe powder metallurgy preparation method of the FeCrAl alloy is different from the example 1 in that: the alloy formulation of this comparative example is shown in Table 1 as number (5) in weight percent with an excess of Y added 2 O 3 An oxide.
Table 1 composition formulations of FeCrAl alloy examples and comparative examples
Performance tests were carried out on the FeCrAl alloys prepared in examples 1-2 and comparative examples 1-5 above, wherein the tensile test method was described in section 1 of the GB/T228.1-2021 metallic material tensile test: room temperature test method and GB/T228.2-2015 metallic materials tensile test part 2: a high temperature test method; high temperature oxidation resistance test reference GB/T13303-91 steel oxidation resistance measuring method. The results are shown in Table 2.
TABLE 2 comparison of Performance tests of FeCrAl alloy examples and comparative examples in accordance with the present invention
The results in table 1 show that the ODS FeCrAl alloy material obtained by optimizing the components and the preparation process in the embodiment of the present invention has good mechanical properties at low temperature and high temperature and excellent oxidation resistance at high temperature: compared with the comparative example, the embodiment achieves the optimized combination of the mechanical property and the high-temperature oxidation resistance of the material.
According to the invention, the ODS FeCrAl alloy material for the nuclear reactor accident fault-tolerant fuel cladding is prepared by a spark plasma sintering method, and the obtained alloy material has better high-temperature mechanical strength, high-temperature oxidation resistance and irradiation resistance through element content optimization and preparation parameter regulation, so that the design requirement can be better met, and the application problem of the FeCrAl alloy material in the nuclear reactor fuel cladding is solved. The invention has the advantages and beneficial effects that: according to the invention, mo, nb, re, Y elements are added on the basis of main constituent elements Cr and Al of the FeCrAl alloy material, and the preferred element content and element addition form are determined. The basic mechanical property and the oxidation resistance of the material are ensured by controlling the contents of Cr and Al elements; adding a proper amount of Mo, nb, re, Y elements and controlling mechanical alloying parameters to form uniformly dispersed fine second phase particles in the alloy, so that the mechanical properties of the alloy are improved; by controlling the proportion of Mo, nb, re and Y elements and the spark plasma sintering parameters, the reduction of mechanical properties caused by coarsening of fine second-phase particles under the influence of long-term high temperature is avoided. The steam oxidation rate of the alloy material obtained by the method under the condition of 1200 ℃ steam is far lower than that of the current commercial nuclear power cladding material Zr-4, and the alloy material has excellent high-temperature oxidation resistance; the second phase particles which are distributed in a tiny dispersion way are formed in the alloy microstructure, so that the mechanical property of the alloy is obviously improved.
The above embodiments are provided to illustrate the technical concept and features of the present invention and are intended to enable those skilled in the art to understand the content of the present invention and implement the same, and are not intended to limit the scope of the present invention. All equivalent changes or modifications made in accordance with the spirit of the present invention should be construed to be included in the scope of the present invention.
Claims (9)
1. The preparation method of the oxide dispersion strengthening FeCrAl alloy is characterized by comprising the following steps of:
mixing the element powder according to the component formula of the FeCrAl alloy, and preparing oxide dispersion strengthening FeCrAl alloy powder by using a mechanical alloying method;
placing the alloy powder into a die, and sintering by using a discharge plasma method to obtain compact blank alloy;
removing the die, and performing high-temperature solution treatment on the compact blank alloy to obtain a solid solution alloy;
forging and hot rolling the solid solution alloy to obtain the oxide dispersion strengthening FeCrAl alloy;
the FeCrAl alloy comprises the following components in percentage by weight: 12.5 to 14.5wt.% Cr,4.5 to 6.0wt.% Al,1.5 to 2.5wt.% Mo,1.0 to 1.5wt.% Nb,0.15 to 0.25wt.% Re,0.10 to 0.15wt.% Y 2 O 3 The balance being Fe and impurity elements.
2. The method according to claim 1, wherein the total weight percentage of Mo and Nb is not less than 3%.
3. The preparation method according to claim 1, wherein the total weight percentage of Re and Y is not less than 0.3%.
4. The method according to claim 1, wherein the ratio of the total weight of Mo and Nb to the total weight of Re and Y is not less than 9.
5. The method according to claim 1, wherein the mechanical alloying ball milling time is 12-18h and the ball-to-material ratio is 10-14:1.
6. The method according to claim 5, wherein the mechanically alloyed ball milling is divided into two stages, wherein in the first stage, the ball milling speed is 80 to 120rpm, and the ball milling time is 1 to 3 hours; in the second stage, the ball milling speed is 200-230 rpm, and the ball milling time is 11-15h.
7. The preparation method according to any one of claims 1 to 6, wherein the temperature rising rate is controlled to be 80-120 ℃/min, the pressure is 40-60MPa, the temperature is 1000-1200 ℃, the sintering time is 15-45min, and the vacuum degree is less than or equal to 0.1Pa in the spark plasma sintering process.
8. An oxide dispersion strengthened FeCrAl alloy prepared according to the method of any one of claims 1-7.
9. Use of an oxide dispersion strengthened FeCrAl alloy prepared by the method of any one of claims 1-7 in nuclear reactor accident tolerant fuel cladding.
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Citations (13)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| CN1258756A (en) * | 1999-12-17 | 2000-07-05 | 黄进峰 | High-temperature high-strength antioxidant anticorrosive austenite alloy |
| CN103938102A (en) * | 2014-05-12 | 2014-07-23 | 盐城市鑫洋电热材料有限公司 | Preparation method of iron, chromium and aluminum multielement electrothermal alloy with high resistance |
| CN106319369A (en) * | 2016-10-12 | 2017-01-11 | 苏州热工研究院有限公司 | FeCrAl base alloy material for nuclear fuel cladding material |
| CN106381448A (en) * | 2016-10-12 | 2017-02-08 | 苏州热工研究院有限公司 | FeCrAl alloy material for nuclear reactor fuel cladding material |
| CN106399846A (en) * | 2016-10-12 | 2017-02-15 | 苏州热工研究院有限公司 | FeCrAl alloy material for preparing Nuclear reactor fuel cladding material |
| CN109811116A (en) * | 2019-02-21 | 2019-05-28 | 中国核动力研究设计院 | A kind of preparation method of crash-proof involucrum FeCrAl based alloy nanocrystalline material |
| CN109988975A (en) * | 2017-12-29 | 2019-07-09 | 中国核动力研究设计院 | The regulation method of disperse nanometer precipitated phase is obtained in a kind of FeCrAl alloy |
| CN110863153A (en) * | 2019-12-05 | 2020-03-06 | 中国核动力研究设计院 | Preparation method of FeCrAl-based ODS alloy material for advanced nuclear fuel element cladding |
| CN110863152A (en) * | 2019-12-05 | 2020-03-06 | 中国核动力研究设计院 | Preparation method of FeCrAl-based ODS alloy for nuclear reactor accident-resistant fuel element cladding |
| CN111809119A (en) * | 2020-07-20 | 2020-10-23 | 中国核动力研究设计院 | Dispersion strengthening FeCrAl alloy material |
| CN113278895A (en) * | 2021-05-06 | 2021-08-20 | 中国科学院合肥物质科学研究院 | High-strength FeCrAl-based alloy |
| CN113564493A (en) * | 2021-08-10 | 2021-10-29 | 成都大学 | High-entropy alloy reinforced FeCrAl alloy cladding material and preparation process thereof |
| WO2022162393A1 (en) * | 2021-01-29 | 2022-08-04 | Oxford Sigma Limited | Nuclear fusion breeder blanket |
-
2022
- 2022-11-04 CN CN202410210845.7A patent/CN117947346A/en active Pending
- 2022-11-04 CN CN202211374399.0A patent/CN115896589B/en active Active
Patent Citations (13)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| CN1258756A (en) * | 1999-12-17 | 2000-07-05 | 黄进峰 | High-temperature high-strength antioxidant anticorrosive austenite alloy |
| CN103938102A (en) * | 2014-05-12 | 2014-07-23 | 盐城市鑫洋电热材料有限公司 | Preparation method of iron, chromium and aluminum multielement electrothermal alloy with high resistance |
| CN106319369A (en) * | 2016-10-12 | 2017-01-11 | 苏州热工研究院有限公司 | FeCrAl base alloy material for nuclear fuel cladding material |
| CN106381448A (en) * | 2016-10-12 | 2017-02-08 | 苏州热工研究院有限公司 | FeCrAl alloy material for nuclear reactor fuel cladding material |
| CN106399846A (en) * | 2016-10-12 | 2017-02-15 | 苏州热工研究院有限公司 | FeCrAl alloy material for preparing Nuclear reactor fuel cladding material |
| CN109988975A (en) * | 2017-12-29 | 2019-07-09 | 中国核动力研究设计院 | The regulation method of disperse nanometer precipitated phase is obtained in a kind of FeCrAl alloy |
| CN109811116A (en) * | 2019-02-21 | 2019-05-28 | 中国核动力研究设计院 | A kind of preparation method of crash-proof involucrum FeCrAl based alloy nanocrystalline material |
| CN110863153A (en) * | 2019-12-05 | 2020-03-06 | 中国核动力研究设计院 | Preparation method of FeCrAl-based ODS alloy material for advanced nuclear fuel element cladding |
| CN110863152A (en) * | 2019-12-05 | 2020-03-06 | 中国核动力研究设计院 | Preparation method of FeCrAl-based ODS alloy for nuclear reactor accident-resistant fuel element cladding |
| CN111809119A (en) * | 2020-07-20 | 2020-10-23 | 中国核动力研究设计院 | Dispersion strengthening FeCrAl alloy material |
| WO2022162393A1 (en) * | 2021-01-29 | 2022-08-04 | Oxford Sigma Limited | Nuclear fusion breeder blanket |
| CN113278895A (en) * | 2021-05-06 | 2021-08-20 | 中国科学院合肥物质科学研究院 | High-strength FeCrAl-based alloy |
| CN113564493A (en) * | 2021-08-10 | 2021-10-29 | 成都大学 | High-entropy alloy reinforced FeCrAl alloy cladding material and preparation process thereof |
Non-Patent Citations (2)
| Title |
|---|
| 活性元素影响MCrAlY涂层氧化性能的研究进展;宋鹏;陆建生;赵宝禄;W.J.Quadakkers;;材料导报(07);59-62 * |
| 燃料包壳用FeCrAl合金变形行为与热加工图研究;柏广海;薛飞;张晏玮;刘二伟;尚灿;刘向兵;耿建桥;余伟炜;;稀有金属材料与工程(07);156-161 * |
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